• Title/Summary/Keyword: 방사성폐기물처분

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Hydrogeological Performance Assessment for Underground Oil Storage Caverns (지하유류비축시설 수리안정성 평가방안)

  • 김천수;배대석;김경수;고용권;송승호
    • The Journal of Engineering Geology
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    • v.7 no.3
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    • pp.229-245
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    • 1997
  • There are Common aspects between the underground oil storage cavern and the radioactive waste disposal facility. Both facilities use appropriately the intrinsic natural berrier characteristics of the rock mass and additionally the engineered barrier system for the long term safety. The geological structures and their hydrogeological characteristics in a faactured rock mass act a major role in the safety and performance of the underground oil storage facility through the design, construction and the operation stages. Because the fracture system distributed in a fractured rock block is complicated owing to their own geometrical and hydrogeological attributes, the hydrogeological perforrmrnce of the facility would depend mainly upon the understandings of their characteristics. This study reviews the uncertainties and key issues which have to be considered to analyse the groundwater flow system in a fractured rock mass and proposes the techniques applicable to characterize the hydrogeological parameter.

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Electrochemical Decontamination of Metallic Wastes Contaminated with Uranium Compounds (우라늄화합물로 오염된 금속폐기물의 전해제염)

  • 양영미;최왕규;오원진;유승곤
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.1 no.1
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    • pp.11-23
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    • 2003
  • A study on the electrolytic dissolution of SUS-304 and Inconel-600 specimen was carried out in neutral salt electrolyte to evaluate the applicability of electrochemical decontamination process for recycle or self disposal with authorization of large amount of metallic wastes contaminated with uranium compounds generated by dismantling a retired uranium conversion plant in Korea. Although the best electrolytic dissolution performance for the specimens was observed in a Na2s04 electrolyte, a NaNO$_3$ neutral salt electrolyte, in which about 30% for SUS-304 and the same for Inconel-600 in the weight loss was shown in comparison with that in a Na$_2$SO$_4$ solution, was selected as an electrolyte for the electrochemical decontamination of metallic wastes with the consideration on the surface of system components contacted with nitric acid and the compatibility with lagoon wastes generated during the facility operation. The effects of current density, electrolytic dissolution time, and concentration of NaNO$_3$ on the electrolytic dissolution of the specimens were investigated. On the basis of the results obtained through the basic inactive experiments, electrochemical decontamination tests using the specimens contaminated with uranium compounds such as UO$_2$, AUC (ammonium uranyl carbonate) and ADU (ammonium diuranate) taken from an uranium conversion facility were performed in 1M NaNO$_3$ solution with the current density or In mA/$\textrm{cm}^2$. it was verified that the electrochemical decontamination of the metallic wastes contaminated uranium compounds was quite successful in a NaNO$_3$ neutral salt electrolyte by reducing $\alpha$ and $\beta$ radioactivities below the level of self disposal within 10 minutes regardless of the type of contaminants and the degree of contamination.

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Analysis of Porosity and Distribution of Pores in Rocks by Micro Focus X-Ray CT (미소 초점 X선 CT를 이용한 암석 내 공극의 분포 및 공극률 분석)

  • Jeong, Gyo-Cheol;Takahashi, Manabu
    • The Journal of Engineering Geology
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    • v.20 no.4
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    • pp.461-465
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    • 2010
  • Weathering and permeability in rocks play a very important role in underground disposal of radioactive waste and their long-term management as well as stability security of rock structures. Weathering and permeability of rocks are largely controlled by the characters of inner structures of rocks. In other words, weathering rate can be accelerated depending on the quantity of pore and microcrack in rocks. Quantitative evaluation of inner structures of rocks can serve as a tool that can assess the degree of weathering of rocks. Therefore it can be said that the understanding of three dimensional distribution of the inner structure of rocks is important for long-term management of rock structures. This study was performed to analyze three dimensional distribution of pore in rocks using Micro Focus X-ray CT on fresh granite and weathered granite from Korea. Results of the analysis clearly show distribution of pore and porosity of the inner rock.

A Methodology to Formulate Stochastic Continuum Model from Discrete Fracture Network Model and Analysis of Compatibility between two Models (개별균열 연결망 모델에 근거한 추계적 연속체 모델의 구성기법과 두 모델간의 적합성 분석)

  • 장근무;이은용;박주완;김창락;박희영
    • Tunnel and Underground Space
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    • v.11 no.2
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    • pp.156-166
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    • 2001
  • A stochastic continuum(SC) modeling technique was developed to simulate the groundwater flow pathway in fractured rocks. This model was developed to overcome the disadvantageous points of discrete fracture network(DFN) modes which has the limitation of fracture numbers. Besides, SC model is able to perform probabilistic analysis and to simulate the conductive groundwater pathway as discrete fracture network model. The SC model was formulated based on the discrete fracture network(DFN) model. The spatial distribution of permeability in the stochastic continuum model was defined by the probability distribution and variogram functions defined from the permeabilities of subdivided smaller blocks of the DFN model. The analysis of groundwater travel time was performed to show the consistency between DFN and SC models by the numerical experiment. It was found that the stochastic continuum modes was an appropriate way to provide the probability density distribution of groundwater velocity which is required for the probabilistic safety assessment of a radioactive waste disposal facility.

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Na Borosilicate Glass Surface Structures: A Classical Molecular Dynamics Simulations Study (소듐붕규산염 유리의 표면 구조에 대한 분자 동역학 시뮬레이션 연구)

  • Kwon, Kideok D.;Criscenti, Louise J.
    • Journal of the Mineralogical Society of Korea
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    • v.26 no.2
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    • pp.119-127
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    • 2013
  • Borosilicate glass dissolution is an important chemical process that impacts the glass durability as nuclear waste form that may be used for high-level radioactive waste disposal. Experiments reported that the glass dissolution rates are strongly dependent on the bulk composition. Because some relationship exists between glass composition and molecular-structure distribution (e.g., non-bridging oxygen content of $SiO_4$ unit and averaged coordination number of B), the composition-dependent dissolution rates are attributed to the bulk structural changes corresponding to the compositional variation. We examined Na borosilicate glass structures by performing classical molecular dynamics (MD) simulations for four different chemical compositions ($xNa_2O{\cdot}B_2O_3{\cdot}ySiO_2$). Our MD simulations demonstrate that glass surfaces have significantly different chemical compositions and structures from the bulk glasses. Because glass surfaces forming an interface with solution are most likely the first dissolution-reaction occurring areas, the current MD result simply that composition-dependent glass dissolution behaviors should be understood by surface structural change upon the chemical composition change.

Elasto-Plastic Analysis of Underground Openings Considering the Effect of Excavation (굴착영향을 고려한 지하공동의 탄소성해석)

  • 최규섭;김대홍;황신일;심재구
    • The Journal of Engineering Geology
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    • v.8 no.3
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    • pp.225-234
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    • 1998
  • The behavior of the underground opening depends mainly on the magnitude of the initial stress existing before excavation and on the stress redistribution due to the excavation. In the case of elasto-plastic materials such as rock mass, as the structural behavior of surrounded opening due to excavation depends on the stress path, methods and sequence of excavation have influences on the results of numerical analysis. Therefore, in order to design underground openings with large cross-section such as underground nuclear power plants, radioactive waste disposal cavems, oil storage caverns, and so on more reasonably it is desirable to consider the effect of the excavation sequence in the analysis. In this paper, the underground structure is analyzed using the finite element method and the distinct element methods with a view to review the the effect of the excavation sequence. Based on the results of the analysis the followings are discussed : influence of excavation shape and sequence, effect of structural reinforcements, influence of multi caverns.

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Collision between Technology and Politics in Korea's Nuclear Policy (한국의 원자력정책을 둘러싼 기술과 정치의 충돌)

  • Hong Jung-Jin;Won Byung-Chul
    • Journal of Science and Technology Studies
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    • v.2 no.1 s.3
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    • pp.135-156
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    • 2002
  • The view of technology is largely divided into 2 theories: (1) the theory of autonomous technology that claims technology's own development logic and momentum, (2) the theory of social determinism that regards technology as reflection of political choices. Autonomous technologists read our society in the language of technology and social determinists read our technology in the language of society. This paper tries to analyze that conflicts between government and environmental group in nuclear policy, especially radioactive waste disposition policy reflect collisions between autonomous technologists and social determinists representing technology and politics, respectively. On the surface, such collisions are occurred in rational, ethical and economical aspects. It maintains, however, in depth, they are about solution means to problems from which technologies derived. Also, it suggests that one of the alternatives to avoid inevitable collision may be interaction approach based on intertwining technology with society. More understanding of political natures and control possibilities for technology is needed because interaction approach is founded on this understanding. Finally, to help forming the Korea's nuclear utilization policy from now on, it gives 2 case studies compared France with Germany where expanding and contracting nuclear utilization policy, respectively.

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Occurrence Characteristics and Existing Forms of U-Th Containing Minerals in KAERI Underground Research Tunnel(KURT) Granite (한국원자력연구원 지하처분연구시설(KURT) 화강암의 U-Th 함유광물 산출특성 및 존재형태)

  • Cho, Wan Hyoung;Baik, Min Hoon;Park, Tae-Jin
    • Economic and Environmental Geology
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    • v.50 no.2
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    • pp.117-128
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    • 2017
  • Occurrence characteristics and existing forms of U-Th containing minerals in KURT (KAERI Underground Research Tunnel) granite are investigated to understand long-term behavior of radionuclides in granite considered as a candidate rock for the geological disposal of high-level radioactive waste. KURT granite primarily consists of quartz, feldspar and mica. zircon, REE(Rare Earth Element)-containing monazite and bastnaesite are also identified. Besides, secondary minerals such as sericite, microcline and chlorite including quartz vein and calcite vein are observed. These minerals are presumed to be accompanied by a post-hydrothermal process. U-Th containing minerals are mainly observed at the boundaries of quartz, feldspar and mica, mostly less than $30{\mu}m$ in size. Quantitative analysis results using EPMA (Electron Probe Micro-Analyzer) show that 74.2 ~ 96.5% of the U-Th containing minerals consist of $UO_2$ (3.39 ~ 33.19 wt.%), $ThO_2$ (41.61 ~ 50.24 wt.%) and $SiO_2$ (15.43 ~ 18.60 wt.%). Chemical structure of the minerals calculated using EPMA quantitative analysis shows that the U-Th minerals are silicate minerals determined as thorite and uranothorite. The U-Th containing silicate minerals are formed by a magmatic and hydrothermal process. Therefore, KURT granite formed by a magmatic differentiation is accompanied by an alteration and replacement owing to a hydrothermal process. U-Th containing silicate minerals in KURT granite are estimated to be recrystallized by geochemical factors and parameters such as temperature, pressure and pH owing to the hydrothermal process. By repeated dissolution/precipitation during the recrystallization process, U-Th containing silicate minerals such as thorite and uranothorite are formed according to the variation in the concentrated amount of U and Th.

Hydraulic-Thermal-Mechanical Properties and Radionuclide Release-Retarding Capacity of Kyungju Bentonite (경주 벤토나이트의 수리-열-역학적 특성 및 핵종 유출 저지능)

  • Jae-Owan Lee;Won-Jin Cho;Pil-Soo Hahn
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.2
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    • pp.87-96
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    • 2004
  • Studies were conducted to select the candidate buffer material for a high-level waste (HLW) repository in Korea. This paper presents the hydraulic properties, the swelling properties, the thermal properties, and the mechanical properties as well as the radionuclide release-retarding capacity of Kyungju bentonite as part of those studies. Experimental results showed that the hydraulic conductivities of the compacted bentonite were very low and less than $10^{-11}$m/s. The values decreased with increasing the dry density of the compacted bentonite. The swelling pressures were in the range of 0.66 MPa to 14.4 ㎫ and they increased with increasing the dry density. The thermal conductivities were in the range of 0.80 ㎉/m $h^{\circ}C$ to 1.52 ㎉/m $h^{\circ}C$. The unconfined compressive strength, Young's modulus and Poison's ratio showed the range of 0.55 ㎫ to 8.83 ㎫, 59 ㎫ to 1275 ㎫, and 0.05 to 0.20, respectively, when the dry densities of the compacted bentonite were 1.4 Ms/㎥ to 1.8 Mg/㎥. The diffusion coefficients in the compacted bentonite were measured under an oxidizing condition. The values were $1.7{\times}10^{-10}$m^2$/s to 3.4{\times}10^{-10}$m^2$/s for electrically neutral tritium (H-3), 8.6{\times}10^{-14}$m^2$/s to 1.3{\times}10^{-12}$m^2$/s for cations (Cs, Sr, Ni), 1.2{\times}10^{-11}$m^2$/s to 9.5{\times}10^{-11}$m^2$/s for anions (I, Tc), and 3.0{\times}10^{-14} $m^2$/s to 1.8{\times}10^{-13}$m^2$/s $for actinides (U, Am), when tile dry densities were in the range of 1.2 Mg/㎥ to 1.8 Mg/㎥. The obtained results will be used in assessing the barrier properties of Kyungju bentonite as a buffer material of a repository in Korea.n Korea.

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Hydraulic Analysis of a Discontinuous Rock Mass Using Smeared Fracture Model and DFN Model (DFN 모델과 스미어드 균열 모델을 이용한 불연속 암반의 3차원 수리해석)

  • Park, Jungchan;Kim, Jin-Seop;Lee, Changsoo;Kwon, Sangki
    • Tunnel and Underground Space
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    • v.29 no.5
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    • pp.318-331
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    • 2019
  • A three-dimensional(3D) equivalent continuum modeling was performed to analyze hydraulic behavior of rock mass considering discontinuities by using DFN model and smeared fracture model. DFN model was generated by FLAC3D and smeared fracture model was applied by using FISH functions, which is built-in functions in FLAC3D, for equivalent continuum model of fractured rock mass. Comparative analysis with 3DEC, which is for discontinuum analysis, was conducted to verify reliability of equivalent continuum analysis by using FLAC3D. Similar results of hydraulic analysis under the same conditions could be achieved. Equivalent continuum analysis of fractured rock mass by using DFN model was implemented to compare with existing analytical methods for inflow into the tunnel.